Impact of He and Cr on defect accumulation in ion-irradiated ultrahigh-purity Fe(Cr) alloys
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In situ electron microscope observations of defects show that the incident high-energy electrons influence the evolution of microstructure of an irradiated material, reducing the number of defects seen in the field of view of the microscope. We investigate ...
2007
In the quest of materials for the first wall of the future fusion reactor, it has been shown that oxide dispersion strengthened (ODS) ferritic / martensitic (F/M) steels appear to be promising candidates. The inherent good mechanical properties supported b ...
Thermonuclear fusion of light atoms is considered since decades as an unlimited, safe and reliable source of energy that could eventually replace classical sources based on fossile fuel or nuclear fuel. Fusion reactor technology and materials studies are i ...
Photoluminescence (PL) spectroscopy has been demonstrated as a suitable technique to characterize Si nanocrystal-based non-volatile memory devices (Carrada et al. APL 2005). These are formed by a single plane of Si nanocrystals (NCs) buried in the gate oxi ...
The theoretical analysis of R-fold modular redundancy, cascaded R-fold modular redundancy and NAND multiplexing is presented and these fault-tolerant techniques are compared in terms of resistance to massive levels of defect density. Optimal cluster size a ...
Irradiation is known to lead to a degradation of the mechanical properties of materials. This is particularly crucial in the case of materials that will be used in the future thermonuclear fusion reactor, where extremely high irradiation doses are expected ...
Understanding radiation-induced defect formation in carbon materials is crucial for nuclear technology and for the manufacturing of nanostructures with desired properties. Using first-principles molecular dynamics, we perform a systematic study of the none ...
Ferritic/martensitic (F/M) steels show good resistance to swelling and low damage accumulation upon irradiation relative to stainless steels. 0.3 wt% yttria particles were added to the F/M steel EUROFER 97 to produce oxide dispersion strengthened (ODS) ste ...
The electrical conductivity of Ce0.992Nb0.008O2−δ was measured as a function of oxygen partial pressure between 10−28 and 1 bar in the temperature range of 873–1173 K. The activation energy for the conductivity at an oxygen partial pressure of 10−4 bar was ...
The effects of neutron irradiation on austenitic stainless steels, usually used for the manufacturing of internal elements of nuclear reactors (e.g. the core shrouds), are the alteration of the microchemistry and the microstructure, and, as a consequence, ...